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Performance of Some Ion-Exchange Resins in Removal of 241Am(III), 152+154Eu(III), 99Mo(VI), 137Cs(I), and 60Co(II) from Simulated Nuclear Acidic Solutions

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Abstract

Separation of 241Am(III), 152+154Eu(III), and 60Co(II) radionuclides from nitric acid solutions by the batch method using KU-2, TRU, and Amberlite® IR-120(H) resins was studied. The separation factors (SFs) of radionuclides are affected by the HNO3 concentration and resin type. In 3 M HNO3, the SF of 152+154Eu from 60Co and 241Am with the KU-2 resin was 628 and 26.48, respectively. In 0.01 M HNO3, the SF of 241Am from 60Co with the TRU resin reached 83. All the resins used showed good radiation resistance and stability up to 100 kGy. Simulated nuclear liquid waste containing minor actinides (241Am), lanthanides (152+154Eu), fission products (137Cs and 99Mo), and activation products (60Co) was successfully treated using column chromatography with the KU-2 resin. The radionuclides were stripped using 1.5 M aqueous HNO3 with 70–82% degree of stripping in one stage. Thus, the KU-2 and TRU resins can be used for treatment of the high level corrosion products containing trivalent long-lived minor actinides (5d elements, e.g., Am and Cm), lanthanides (4f elements) and/or divalent heavy metals (3d elements), associated with a nuclear power plant.

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Authors and Affiliations

  1. Department of Analytical Chemistry and Control, Hot Laboratories Center, Egyptian Atomic Energy Authority, 13759, Cairo, Egypt

    M. F. Attallah, E. M. El Afifi & F. A. Shehata

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  1. M. F. Attallah
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  2. E. M. El Afifi
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  3. F. A. Shehata
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Correspondence to M. F. Attallah.

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Attallah, M.F., Afifi, E.M.E. & Shehata, F.A. Performance of Some Ion-Exchange Resins in Removal of 241Am(III), 152+154Eu(III), 99Mo(VI), 137Cs(I), and 60Co(II) from Simulated Nuclear Acidic Solutions. Radiochemistry 62, 681–688 (2020). https://doi.org/10.1134/S1066362220050161

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